SPERT PROJECT. Quarterly Technical Report, April--June 1967.
Technical Report
·
OSTI ID:4502182
- ed.
- Research Organization:
- Phillips Petroleum Co., Idaho Falls, Idaho. Atomic Energy Div.
- DOE Contract Number:
- AT(10-1)-205
- NSA Number:
- NSA-22-044890
- OSTI ID:
- 4502182
- Report Number(s):
- IDO--17270
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ANALYSIS
CONTROL ELEMENTS
CONTROL SYSTEMS
FUEL ELEMENTS
HYDRAULICS
MACHINE PARTS
N38570* --Research & Test Reactors & Critical Assemblies-- Operation
PBF
PERFORMANCE
POWER BURST FACILITY/ control system for
testing of prototype hydraulic transient rod drive for
(E/T)
REACTIVITY
REACTIVITY/step insertions in uranium oxide (UO$sub 2$)-fueled Spert 3 Oxide Core Kinetics Test E-core
effects on transient behavior of 0.67 to 1.25$
(E/T)
REACTOR CORE
REACTOR SAFETY EXPERIMENTS/transient behavior of Spert 4 Capsule Driver Core
analysis of short period
(E)
REACTOR SAFETY EXPERIMENTS/transient behavior of uranium oxide (UO$sub 2$)-fueled Spert 3 Oxide Core Kinetics Test E-core
analysis of 0.67 to 1.25$ step reactivity
(E/T)
RESEARCH REACTORS
SPERT-3
SPERT-4
TESTING
TRANSIENTS
CONTROL ELEMENTS
CONTROL SYSTEMS
FUEL ELEMENTS
HYDRAULICS
MACHINE PARTS
N38570* --Research & Test Reactors & Critical Assemblies-- Operation
PBF
PERFORMANCE
POWER BURST FACILITY/ control system for
testing of prototype hydraulic transient rod drive for
(E/T)
REACTIVITY
REACTIVITY/step insertions in uranium oxide (UO$sub 2$)-fueled Spert 3 Oxide Core Kinetics Test E-core
effects on transient behavior of 0.67 to 1.25$
(E/T)
REACTOR CORE
REACTOR SAFETY EXPERIMENTS/transient behavior of Spert 4 Capsule Driver Core
analysis of short period
(E)
REACTOR SAFETY EXPERIMENTS/transient behavior of uranium oxide (UO$sub 2$)-fueled Spert 3 Oxide Core Kinetics Test E-core
analysis of 0.67 to 1.25$ step reactivity
(E/T)
RESEARCH REACTORS
SPERT-3
SPERT-4
TESTING
TRANSIENTS